CN204044016U - Material test apparatus under a kind of nuclear power station steam leakage simulated condition - Google Patents
Material test apparatus under a kind of nuclear power station steam leakage simulated condition Download PDFInfo
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- CN204044016U CN204044016U CN201420430298.5U CN201420430298U CN204044016U CN 204044016 U CN204044016 U CN 204044016U CN 201420430298 U CN201420430298 U CN 201420430298U CN 204044016 U CN204044016 U CN 204044016U
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Abstract
The utility model relates to the material test apparatus under a kind of nuclear power station steam leakage simulated condition, comprises Leak Off Test (LOT) stove, steam generator, peripheral cooling water tank and BAS case; Steam generator is connected to the top of Leak Off Test (LOT) stove by pipeline, peripheral cooling water tank is connected to the top of Leak Off Test (LOT) stove near middle position by pipeline, BAS case is connected to the bottom of Leak Off Test (LOT) stove by pipeline, the flange short tube at the top of Leak Off Test (LOT) stove is provided with the pipeline with safety valve, the pipeline that the flange short tube of the bottom of Leak Off Test (LOT) stove connects is divided into the pipeline of blow-off line and discharge boric acid.In the utility model, Leak Off Test (LOT) furnace volume is less, requires corresponding reduction to the supply of steam, borate, is conducive to promoting in nuclear industry institute.Adopt flash distillation mode to produce steam, avoid external Leak Off Test (LOT) stove and must depend on the limitation carrying out testing in fuel-burning power plant, inner employing demountable structure, for the adjustment of operating condition of test creates condition.
Description
Technical field
The utility model relates to a kind of material test apparatus, and it is less to be specifically related to a kind of test unit volume, must depend on fuel-burning power plant and test, and is conducive to the material test apparatus under the nuclear power station steam leakage simulated condition promoted in nuclear industry institute.
Background technology
Domestic existing nuclear power station technology, substantially by abroad introducing, the pipeline outer wall protective finish material that nuclear power station inside adopts also all overlaps the synchronous import of technical standard by first wife.Because the coating material of China's exploitation cannot obtain the technical appraisement of external authoritative institution, the technology of this type of home made materials is identified with failing and is used always in engineering.Especially along with the propelling of the Generation Ⅲ ACP1000 of Chinese independent research, the test of nuclear power station conventional island part steam-water pipe outer wall protective finish material and qualification are badly in need of synchronously carrying out, otherwise can only continue to walk the old road from external import.
Utility model content
For the problems referred to above, it is less that fundamental purpose of the present utility model is to provide a kind of test unit volume, must depend on fuel-burning power plant and test, and is conducive to the material test apparatus under the nuclear power station steam leakage simulated condition promoted in nuclear industry institute.
The utility model solves above-mentioned technical matters by following technical proposals: the material test apparatus under a kind of nuclear power station steam leakage simulated condition, described material test apparatus comprises Leak Off Test (LOT) stove, steam generator, peripheral cooling water tank and BAS case.
Described Leak Off Test (LOT) stove comprise a cylindrical tube, cylindrical tube be two axiolitic end sockets up and down, be respectively upper cover and low head, total adopts the some support leg pipes be welded on low head to support, and top and the bottom of Leak Off Test (LOT) stove all have flange short tube.
Described steam generator is connected to the top of Leak Off Test (LOT) stove by pipeline, peripheral cooling water tank is connected to the top of Leak Off Test (LOT) stove near middle position by pipeline, BAS case is connected to the bottom of Leak Off Test (LOT) stove by pipeline, the flange short tube at the top of Leak Off Test (LOT) stove is provided with the pipeline with safety valve, the pipeline that the flange short tube of the bottom of Leak Off Test (LOT) stove connects is divided into two, is respectively the pipeline and the pipeline being provided with boric acid bleed valve that are provided with blowoff valve.
Described steam generator comprises flash tank, the saturated water pot of electrical heating high pressure is gentle rushes tank; Flash tank is connected on surge tank by pipeline, and surge tank is connected on the saturated water pot of electrical heating high pressure by pipeline, and the saturated water pot of electrical heating high pressure connects flash tank by pipeline.
Flash tank is provided with the lateral being divided into some branches, in lateral wherein one be connected on BAS case, be connected on Leak Off Test (LOT) stove by steam main valve after remaining lateral is connected into one, each of lateral is all provided with steam valve.
Peripheral cooling water tank is provided with the lateral being divided into some branches, be connected on Leak Off Test (LOT) stove after one on wherein one and BAS case in the lateral pipeline being provided with boric acid ebullator merges, remaining lateral is connected to after being connected into one on Leak Off Test (LOT) stove, and each of lateral is all provided with cooling water valve.
Steam after described steam generator is sprayed by steam injection equipment after entering Leak Off Test (LOT) stove.
In preferred embodiment of the present utility model, described support leg pipe has three, and the weld between support leg pipe and low head is provided with stiffening plate, and upper cover welded top has the hanger whole Leak Off Test (LOT) stove can sling.
In preferred embodiment of the present utility model, the bottom welding of described support leg pipe has support foot plate.
In preferred embodiment of the present utility model, described steam injection equipment comprises nozzle holder and nozzle, and nozzle is fixedly mounted on nozzle holder, and nozzle holder is connected on the pipeline of steam.
In preferred embodiment of the present utility model, described Leak Off Test (LOT) stove be provided with two liquid level gauges and have a fluid infusion mouth.
Positive progressive effect of the present utility model is: the test unit volume in the utility model is less, requires corresponding reduction to the supply of steam, borate, is conducive to promoting in nuclear industry institute.
Test unit in the utility model adopts flash distillation mode to produce steam, avoids external Leak Off Test (LOT) stove stove and must depend on the limitation carrying out testing in fuel-burning power plant.
Test unit inside in the utility model adopts demountable structure, for the adjustment of operating condition of test creates condition.
The steam transmission & distribution of the test unit in the utility model and control methods, and the transmission & distribution of borate and control methods, adopt non-linear step automatically to control, be convenient to the detailed process of control system record process of the test.
Accompanying drawing explanation
Fig. 1 is the external structure schematic diagram of Leak Off Test (LOT) stove of the present utility model.
Fig. 2 is the one-piece construction schematic diagram of whole material test apparatus.
Embodiment
The utility model preferred embodiment is provided, to describe the technical solution of the utility model in detail below in conjunction with accompanying drawing.
Fig. 1 is the external structure schematic diagram of Leak Off Test (LOT) stove of the present utility model, Leak Off Test (LOT) stove 100 comprises a cylindrical tube 5, cylindrical tube 5 be two axiolitic end sockets up and down, be respectively upper cover 3 and low head 4, total adopts the support leg pipe 7 be welded on low head 4 to support, in the examples of implementation that Fig. 1 gives, support leg pipe 7 has three, weld between support leg pipe 7 and low head 4 is provided with stiffening plate 6, in order to evenly stressed, usually support foot plate 8 is had at the bottom welding of support leg pipe 7, upper cover 3 welded top has the hanger 2 whole Leak Off Test (LOT) stove can sling, the top of Leak Off Test (LOT) stove and bottom all have flange short tube 1.
Fig. 2 is the one-piece construction schematic diagram of whole material test apparatus, as shown in Figure 2: the Leak Off Test (LOT) stove 100 that comprises in Fig. 2 comprises the fluid infusion mouth 9 do not illustrated in Fig. 1, on flange short tube 1 install safety valve 10 and blowdown, Drainage pipe 11.Also comprise in fig. 2: steam generator 200, peripheral chilled water unit 300, BAS case 400.
Steam generator 200 is connected to the top of Leak Off Test (LOT) stove 100 by pipeline, peripheral cooling water tank 300 is connected to the top of Leak Off Test (LOT) stove 100 near middle position by pipeline, BAS case 400 is connected to the bottom of Leak Off Test (LOT) stove 100 by pipeline, the flange short tube 1 at the top of Leak Off Test (LOT) stove 100 is provided with the pipeline with safety valve 10, the pipeline that the flange short tube 1 of the bottom of Leak Off Test (LOT) stove 100 connects is divided into two, is respectively the pipeline and the pipeline being provided with boric acid bleed valve 13 that are provided with blowoff valve 12.
Steam generator 200 comprises flash tank 14, the saturated water pot 15 of electrical heating high pressure and surge tank 16; Flash tank 14 is connected on surge tank 16 by pipeline, and surge tank 16 is connected on the saturated water pot 15 of electrical heating high pressure by pipeline, and the saturated water pot 15 of electrical heating high pressure connects flash tank 14 by pipeline.
Flash tank 14 is provided with the lateral being divided into some branches, in lateral wherein one be connected on BAS case 400, be connected on Leak Off Test (LOT) stove 100 by steam main valve 17 after remaining lateral is connected into one, each of lateral is all provided with steam valve 18.
Peripheral cooling water tank 300 is provided with the lateral being divided into some branches, be connected on Leak Off Test (LOT) stove 1 after one on wherein one and BAS case 400 in the lateral pipeline being provided with boric acid ebullator 19 merges, remaining lateral is connected to after being connected into one on Leak Off Test (LOT) stove 1, and each of lateral is all provided with cooling water valve 20.
Steam after steam generator 200 is sprayed by steam injection equipment after entering Leak Off Test (LOT) stove 100.Steam injection equipment comprises nozzle holder 21 and nozzle 22, and nozzle 22 is fixedly mounted on nozzle holder 21, and nozzle holder 21 is connected on the pipeline of steam.
Leak Off Test (LOT) stove 100 be provided with two liquid level gauges 23 and have a fluid infusion mouth 9.
In concrete implementation process of the present utility model, Leak Off Test (LOT) stove 100 is the vertical pressure vessel of 316L stainless steel material, sees Fig. 1.Leak Off Test (LOT) stove 100 outside surface needs coated heat-insulation layer.This Leak Off Test (LOT) stove 100 can simulate the operating condition of containment inside under primary Ioops large-break LOCA operating mode: inject steam by steam inlet is a large amount of rapidly toward pressure vessel inside, internal tank temperature is made to rise to rapidly maximum temperature 160 DEG C, then automatically start spray system to show to spray the boric acid water that pH is 4.3 to the inner sample of pressure vessel, the temperature and pressure in pressure vessel is slowly reduced.Spray system is fetched water from pressure vessel bottom water intaking ozzle, is realized circulated sprinkling by nozzle 22 again, and spray system has a refrigeratory, can realize the cooling of shower water.Water-level gauge can monitor internal tank water level, waterlevel data can be sent to central control system, and can carry out lowest water level (preventing ebullator from dallying) and peak level (preventing sample from being soaked) warning.The effect of bottom steam inlet nipple utilizes steam to heat boric acid water at the test initial stage.Temp probe ozzle and pressure probe ozzle can realize the monitoring to pressure vessel internal temperature and pressure.
More than show and describe ultimate principle of the present utility model and principal character and advantage of the present utility model.The technician of the industry should understand; the utility model is not restricted to the described embodiments; what describe in above-described embodiment and instructions just illustrates principle of the present utility model; under the prerequisite not departing from the utility model spirit and scope; the utility model also has various changes and modifications; these changes and improvements all fall within the scope of claimed the utility model, and the claimed scope of the utility model is defined by appending claims and equivalent thereof.
Claims (5)
1. the material test apparatus under nuclear power station steam leakage simulated condition, is characterized in that: described material test apparatus comprises Leak Off Test (LOT) stove, steam generator, peripheral cooling water tank and BAS case;
Described Leak Off Test (LOT) stove comprise a cylindrical tube, cylindrical tube be two axiolitic end sockets up and down, be respectively upper cover and low head, total adopts the some support leg pipes be welded on low head to support, and top and the bottom of Leak Off Test (LOT) stove all have flange short tube;
Described steam generator is connected to the top of Leak Off Test (LOT) stove by pipeline, peripheral cooling water tank is connected to the top of Leak Off Test (LOT) stove near middle position by pipeline, BAS case is connected to the bottom of Leak Off Test (LOT) stove by pipeline, the flange short tube at the top of Leak Off Test (LOT) stove is provided with the pipeline with safety valve, the pipeline that the flange short tube of the bottom of Leak Off Test (LOT) stove connects is divided into two, is respectively the pipeline and the pipeline being provided with boric acid bleed valve that are provided with blowoff valve;
Described steam generator comprises flash tank, the saturated water pot of electrical heating high pressure is gentle rushes tank; Flash tank is connected on surge tank by pipeline, and surge tank is connected on the saturated water pot of electrical heating high pressure by pipeline, and the saturated water pot of electrical heating high pressure connects flash tank by pipeline;
Flash tank is provided with the lateral being divided into some branches, in lateral wherein one be connected on BAS case, be connected on Leak Off Test (LOT) stove by steam main valve after remaining lateral is connected into one, each of lateral is all provided with steam valve;
Peripheral cooling water tank is provided with the lateral being divided into some branches, be connected on Leak Off Test (LOT) stove after one on wherein one and BAS case in the lateral pipeline being provided with boric acid ebullator merges, remaining lateral is connected to after being connected into one on Leak Off Test (LOT) stove, and each of lateral is all provided with cooling water valve;
Steam after described steam generator is sprayed by steam injection equipment after entering Leak Off Test (LOT) stove.
2. the material test apparatus under nuclear power station steam leakage simulated condition according to claim 1, it is characterized in that: described support leg pipe has three, weld between support leg pipe and low head is provided with stiffening plate, and upper cover welded top has the hanger whole Leak Off Test (LOT) stove can sling.
3. the material test apparatus under nuclear power station steam leakage simulated condition according to claim 2, is characterized in that: the bottom welding of described support leg pipe has support foot plate.
4. the material test apparatus under nuclear power station steam leakage simulated condition according to claim 1, it is characterized in that: described steam injection equipment comprises nozzle holder and nozzle, nozzle is fixedly mounted on nozzle holder, and nozzle holder is connected on the pipeline of steam.
5. the material test apparatus under nuclear power station steam leakage simulated condition according to claim 1, is characterized in that: described Leak Off Test (LOT) stove be provided with two liquid level gauges and have a fluid infusion mouth.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420430298.5U CN204044016U (en) | 2014-07-31 | 2014-07-31 | Material test apparatus under a kind of nuclear power station steam leakage simulated condition |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201420430298.5U CN204044016U (en) | 2014-07-31 | 2014-07-31 | Material test apparatus under a kind of nuclear power station steam leakage simulated condition |
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| Publication Number | Publication Date |
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| CN204044016U true CN204044016U (en) | 2014-12-24 |
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| Application Number | Title | Priority Date | Filing Date |
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| CN201420430298.5U Expired - Fee Related CN204044016U (en) | 2014-07-31 | 2014-07-31 | Material test apparatus under a kind of nuclear power station steam leakage simulated condition |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104505131A (en) * | 2015-01-19 | 2015-04-08 | 中国核动力研究设计院 | Crevasse simulation system with two-phase discharge flow measurement function and measurement method thereof |
| CN104538067A (en) * | 2015-01-19 | 2015-04-22 | 中国核动力研究设计院 | Dismountable cleavage simulating part as well as installation method and cleavage simulation system of dismountable cleavage simulating part |
| CN113436492A (en) * | 2021-06-22 | 2021-09-24 | 中国舰船研究设计中心 | High-energy pipeline break accident simulation device |
| CN114264416A (en) * | 2021-12-24 | 2022-04-01 | 西安交通大学 | Test system and method for researching internal leakage of steam generator |
-
2014
- 2014-07-31 CN CN201420430298.5U patent/CN204044016U/en not_active Expired - Fee Related
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104505131A (en) * | 2015-01-19 | 2015-04-08 | 中国核动力研究设计院 | Crevasse simulation system with two-phase discharge flow measurement function and measurement method thereof |
| CN104538067A (en) * | 2015-01-19 | 2015-04-22 | 中国核动力研究设计院 | Dismountable cleavage simulating part as well as installation method and cleavage simulation system of dismountable cleavage simulating part |
| CN104538067B (en) * | 2015-01-19 | 2016-08-31 | 中国核动力研究设计院 | Removable cut simulating piece and installation method thereof and cut simulation system |
| CN113436492A (en) * | 2021-06-22 | 2021-09-24 | 中国舰船研究设计中心 | High-energy pipeline break accident simulation device |
| CN114264416A (en) * | 2021-12-24 | 2022-04-01 | 西安交通大学 | Test system and method for researching internal leakage of steam generator |
| CN114264416B (en) * | 2021-12-24 | 2022-08-26 | 西安交通大学 | Test system and method for researching internal leakage of steam generator |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20141224 Termination date: 20190731 |